Letter Sequence Acceptance Review |
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MONTHYEARML15336A0832015-09-30030 September 2015
WCAP-18030-NP, Revision 0, Criticality Safety Analysis for Palo Verde Nuclear Generating Station, Units 1, 2, and 3
Project stage: Request
ML15329A2282015-11-25025 November 2015
Submits Change to Degraded Voltage License Amendment Request Submittal Commitment Date
Project stage: Request
ML15336A0872015-11-25025 November 2015
License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis
Project stage: Request
ML16012A0032016-01-11011 January 2016
Draft Unacceptable with Opportunity to Supplement Requested Licensing Action Email, Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis
Project stage: Draft Other
ML16014A0012016-01-15015 January 2016
Supplemental Information Needed for Acceptance of Requested Licensing Action, Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis
Project stage: Acceptance Review
ML16043A3612016-01-29029 January 2016
Supplemental Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis
Project stage: Supplement
ML16043A3892016-02-18018 February 2016
Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis
Project stage: Acceptance Review
ML16155A0752016-06-0202 June 2016
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Aphb and Esgb RAIs for Spent Fuel Pool Criticality Safety Analysis LAR
Project stage: RAI
ML16182A5192016-06-30030 June 2016
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Critical Safety Analysis
Project stage: Response to RAI
ML16197A0062016-07-14014 July 2016
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs from Snpb for LAR That Requested Revision to TSs to Incorporate Updated Criticality Safety Analysis
Project stage: RAI
ML16286A2402016-10-0606 October 2016
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis
Project stage: Response to RAI
ML16321A0022016-11-0909 November 2016
Response to RAI, Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis - Revised Technical Specifications and Bases and WCAP-18030, Revision 1
Project stage: Response to RAI
ML17167A2152016-11-23023 November 2016
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis - Revised .
Project stage: Response to RAI
ML17062B0362017-03-0303 March 2017
Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis
Project stage: Supplement
ML17144A3762017-05-24024 May 2017
Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis
Project stage: Supplement
ML17145A2732017-06-15015 June 2017
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML17188A4122017-07-28028 July 2017
Issuance of Amendment Nos. 203, 203, and 203 to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis
Project stage: Approval
2016-11-09
[Table View] |
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Category:Acceptance Review Letter
MONTHYEARML25003A1752024-12-30030 December 2024
Relief Request 73- Proposed Alternative for Pressurizer Lower Shell Temperature Nozzle Life of Repair
ML24326A2002024-11-20020 November 2024
Acceptance Review of Palo Verde Valve Relief Request (VRR) - 02
ML24248A2632024-09-0404 September 2024
Acceptance Review of Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Relief Request (RR) No. 71: Re?Submittal of RR?30
ML24120A2612024-05-0101 May 2024
Email Acceptance Review of Requested Licensing Action License Renewal Commitment 23A, Alloy 600 Management Program Plan
ML24103A1222024-04-11011 April 2024
– Acceptance of Requested Licensing Action Re_ License Amendment Request to Revise Technical Specifications 3
ML18312A3322018-11-13013 November 2018
Acceptance Review for License Amendment and Exemption Requests Regarding the Implementation of Framatome High Thermal Performance Fuel
ML16043A3892016-02-18018 February 2016
Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis
ML16012A0032016-01-11011 January 2016
Draft Unacceptable with Opportunity to Supplement Requested Licensing Action Email, Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis
ML15303A0982015-11-0909 November 2015
Acceptance Review Letter, License Amendment Request, Adopt Technical Specification Task Force (TSTF)-505, Revision 1, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4b
ML15113A6362015-04-22022 April 2015
Acceptance of Relief Request 53
ML13358A0492013-12-24024 December 2013
Acceptance Review Following Supplement, License Amendment Request to Revise TS 3.3.3, Control Element Assembly Calculators and TS 3.3.6, Engineered Safety Features Actuation System (ESFAS) Logic and Manual Trip
ML13247A5512013-09-0404 September 2013
Acceptance Review E-mail, Review of Pressurized-Water Reactor Internal Aging Management Program Plan
ML13032A5372013-02-0101 February 2013
Acceptance Review Email, License Amendment Request to Adopt TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360
ML13025A2482013-01-25025 January 2013
Acceptance Review Email, License Amendment Request to Adopt TSTF-490, Revision 0, Deletion of E-Bar Definition and Revision to RCS Specific Activity Technical Specifications
ML12243A4662012-08-30030 August 2012
Acceptance Review Results Email - for Relief Request Related to Phased Array Ultrasonic Examination Techniques
ML1213103802012-05-10010 May 2012
Acceptance Review Email, License Amendment Request to Revise Technical Specifications to Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Revision 3
ML1202703432012-01-27027 January 2012
Acceptance Review Email, Request for Relief to Use Subsequent Edition/Addenda of ASME Code Section XI, for the 3rd 10-Year Inservice Inspection Interval
ML1201800792012-01-18018 January 2012
Acceptance Review Email, Request for Approval of Proposed Changes to Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules
IR 05000529/20110012011-12-16016 December 2011
Acceptance Review E-mail, License Amendment Request to Modify Technical Specifications to Implement Administrative Changes Including Corrective Actions from U2 Event in LER 50-529/2011-001
ML1113101402011-05-11011 May 2011
Acceptance Review Email, Adoption of Technical Specification Task Force (TSTF)-425, Rev. 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b
ML1027102522010-09-28028 September 2010
Acceptance Review E-mail, License Amendment Request to Revise Updated Final Safety Analysis Report, Feedwater Line Break Analysis with LOOP and Single Failure Analysis
ML1022405612010-08-12012 August 2010
Acceptance Review Email LAR for Cyber Security Plan
ML1018102662010-06-30030 June 2010
Acceptance Review Email, License Amendment Request, Adoption of TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications
ML1014404042010-05-24024 May 2010
Acceptance Review Email, License Amendment Request, Revise Technical Specification (TS) 2.2, Safety Limit Violations, and TS 5.2.1, Onsite and Offsite Organizations to Adopt TSTF-5 and TSTF-65
ML1014404232010-05-24024 May 2010
Acceptance Review Email LAR to Revise TS 5.5.8, Inservice Testing Program (TAC Nos., ME3914/5/6)
ML1006807152010-03-0909 March 2010
Acceptance Review Email, Request for Exemption from 10 CFR Part 73, Physical Security Requirements
ML1001404542010-01-14014 January 2010
Acceptance Review Email, License Amendment Request to Revise Technical Specification Table 3.3.5-1, Engineered Safety Features Actuation System, and Figure 3.5-1, Minimum Refueling Water Tank Volume (TAC ME2842-ME2844)
ML0935212592009-12-18018 December 2009
Acceptance Review Email, Request for Temporary Exemption from the Provisions of 10 CFR 50.46 and 10 CFR 50, Appendix K for Lead Fuel Assemblies
ML0934307842009-12-0909 December 2009
Acceptance Review Email, License Amendment Request to Revise License Condition for Maximum Power Level and Miscellaneous Technical Specification Changes
ML0932302872009-11-19019 November 2009
Email, Acceptance Review, Relief Request No. 45 from Certain ASME Code Class 1 Weld and Component Volumetric Exams of Reactor Vessel Outlet Nozzles for Second 10-Year Inservice Inspection Interval
ML0931601922009-11-12012 November 2009
Acceptance Review Email, License Amendment Request, Revise Technical Specification 3.8.7, Inverters - Operating, to Extend Completion Time for Restoration of Inoperable Inverter
ML0929501942009-10-22022 October 2009
Acceptance Review Email Relief Request No. 44, for Third 10-year Inservice Inspection Interval
ML0919503422009-07-14014 July 2009
Acceptance Review Email, Relief Request No. 40, Deferral of Reactor Vessel Weld Inspection Frequency
ML0918107982009-06-30030 June 2009
Acceptance Review Email, Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26
ML0909102162009-04-0101 April 2009
Acceptance Review Email, Request for Exemption from Sections of 10 CFR 55, Operators Licenses
ML0909101852009-04-0101 April 2009
Acceptance Review Email, License Amendment Request to Relocate RCS Pressure/Temperature Limits from Technical. Specifications to Technical Requirements Manual and Exemption Request from 10 CFR 50 Appendix G
ML0906906552009-03-10010 March 2009
Acceptance Review Email, Relief Request No. 41 to Allow Use of Appendix I of Code Case N-729-1 for Remainder of Third 10-year Inservice Inspection Interval
ML0904303902009-02-12012 February 2009
Acceptance Review Email, Relief Request 43 for Second 10-year Inservice Inspection Interval
ML0904200552009-02-11011 February 2009
Acceptance Review E-mail License Amendment Requests for Hydrogen Monitoring
ML0833802942008-12-0303 December 2008
Acceptance Review E-Mail, License Amendment Request to Revise TS 3.5.5 to Increase the Refueling Water Tank Minimum Water Level
ML0830802872008-11-0303 November 2008
Acceptance Review of Application to Modify Technical Specification 5.5.16, Containment Leakage Rate Testing Program, Risk-Informed
ML0828407002008-10-0909 October 2008
Acceptance Review Email, License Amendment Request to Revise TS 5.6.5, Core Operating Limits Report (COLR)
ML0900801172008-09-0505 September 2008
Acceptance Review Email, License Amendment Request, Revise Technical Specification 4.2.2, Control Element Assemblies
ML0824609552008-08-28028 August 2008
Email Relief Request 39
2024-09-04
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Randall K. Edington Executive Vice President Nuclear/
Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034 February 18, 2016
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3-ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO INCORPORATE UPDATED CRITICALITY SAFETY ANALYSIS (CAC NOS.
MF7138, MF7139, AND MF7140)
Dear Mr. Edington:
By letter dated November 25, 2015, as supplemented by letter dated January 29, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML15336A251 and ML16043A361), Arizona Public Service Company (APS, the licensee) submitted a license amendment request for Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The proposed amendment would modify technical specification (TS) requirements to incorporate the results of an updated criticality safety analysis for both new and spent fuel storage. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
If you have any questions, please contact me at (301) 415-1233 or via e-mail at Margaret.Watford@nrc.gov.
Docket Nos. STN 50-528, STN 50-529, and STN 50-530 cc: Distribution via Listserv Sincerely, 11
(}7l0cLt~ij Margaret M. Watfora, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML16043A389 OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1 /LA NAME MWatford JBurkhardt DATE 2/17/16 2/16/16 Sincerely, IRA/
Margaret M. Watford, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- via email NRR/DSS/SNPB/BC NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1 /PM JDean*
RPascarelli MWatford 2/11/16 2/18/16 2/18/16
